• 제목/요약/키워드: Fuel Claddings

검색결과 51건 처리시간 0.031초

Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

  • Kiraly, M.;Hozer, Z.;Horvath, M.;Novotny, T.;Perez-Fero, E.;Ver, N.
    • Nuclear Engineering and Technology
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    • 제51권2호
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    • pp.518-525
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    • 2019

  • The mechanical and corrosion behavior of the Russian zirconium fuel cladding alloy E110, predominantly used in VVERs, has been investigated for many decades. The recent commercialization of a new, optimized E110 alloy, produced on a sponge zirconium basis, gave the opportunity to compare the mechanical properties of the old and the new E110 fuel claddings. Axial and tangential tensile test experiments were performed with samples from both claddings in the MTA EK. Due to the anisotropy of the cladding tubes, the axial tensile strength was 10-15% higher than the tangential (measured by ring tensile tests). The tensile strength of the new E110G alloy was 11% higher than that of the E110 cladding at room temperature. Some samples underwent chemical treatment - slight oxidation in steam or hydrogenation - or heat treatment - in argon atmosphere at temperatures between 600 and $1000^{\circ}C$. The heat treatment during the oxidation had more significant effect on the tensile strength of the claddings than the oxidation itself, which lowered the tensile strength as the thickness of the metal decreased. The hydrogenation of the cladding samples slightly lowered the tensile strength and the samples but they remained ductile even at room temperature.

  • https://doi.org/10.1016/j.net.2018.11.002 인용 PDF KSCI

Nb가 첨가된 신형 지르코늄 피복관의 열적 크리프 거동 (Thermal Creep Behavior of Advanced Zirconium Claddings Contained Niobium)

  • 김준환;방제건;정용환
    • 한국재료학회지
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    • 제14권7호
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    • pp.451-456
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    • 2004

  • Thermal creep properties of the zirconium tube which was developed for high burnup application were evaluated. The creep test of cladding tubes after various final heat treatment was carried out by the internal pressurization method in the temperature range from $350^{\circ}C to 400^{\circ}C$ and from 100 to 150 MPa in the hoop stress. Creep tests were lasted up to 900days, which showed the steady-state secondary creep rate. The creep resistance of zirconium claddings was higher than that of Zircaloy-4. Factors that affect creep resistance, such as final annealing temperature, applied stress and alloying element were discussed. Tin as an alloying element was more effective than niobium due to solute hardening effect of tin. In case of advanced claddings, the optimization of final heat treatment temperature as well as alloying element causes a great influence on the improvement of creep resistance.

  • https://doi.org/10.3740/MRSK.2004.14.7.451 인용 PDF KSCI

Zircaloy-4 핵연료 피복관의 신파괴인성 시험법 (New Fracture Toughness Test Method of Zircaloy-4 Nuclear Fuel Cladding)

  • 오동준;안상복;홍권표
    • 대한기계학회논문집A
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    • 제27권5호
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    • pp.823-832
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    • 2003

  • To define the causes of cladding degradation which can take place during the operation of nuclear power plants, it is required to develop the new fracture toughness test of spent fuel cladding. The fracture toughness of Zircaloy-4 cladding was estimated using the recently developed KAERI embedded Charpy (KEC) specimen. Axially notched KEC specimens cut directly from unirradiated fuel claddings, were tested in a way similar to the standard toughness test method of a Single Edge Bending (SEB) specimen. The results of KEC fracture toughness test at room temperatures were discussed and compared with those of the previous other studies. In conclusions, even though the KEC fracture toughness test of nuclear fuel claddings was easier and more reliable than those developed earlier, the results from the cladding fracture tests were not the material characteristics but the specific fracture parameters which were deeply related to the specification of claddings. In addition, the phenomenon of a thickness yielding was not observed from the fracture surface. It was closely related to the fact that the plane strain condition of the KEC specimen was changed to the plane stress condition during crack advancing. It was also supported by the fractographic evidence that the formation of ductile dimples at the crack initiation became the similar appearance such as a quasi-cleavage after the sufficient crack advancing.

  • https://doi.org/10.3795/KSME-A.2003.27.5.823 인용 PDF KSCI